|
|
Line 49: |
Line 49: |
| : 1. (Docket I;o. 50-275 - Diablo Canyon PcAR, 3rd Eupplement, Quention V. B. I.) (Docket No. 50-295 - Zion PSAR, Vol. 3, Queation V. B. I.) | | : 1. (Docket I;o. 50-275 - Diablo Canyon PcAR, 3rd Eupplement, Quention V. B. I.) (Docket No. 50-295 - Zion PSAR, Vol. 3, Queation V. B. I.) |
| " Provide a detail '. O ccucsion of the experimental programs which are in progress or will be accomplished prior to operation to demonstrate the proposed core can be safely operated at a linear power generation rate of 18 9 kw/ft and withstand levels of 213 kw/ft without fuel failure during operating tranciente at the nnxirnum expected fuel exposure." | | " Provide a detail '. O ccucsion of the experimental programs which are in progress or will be accomplished prior to operation to demonstrate the proposed core can be safely operated at a linear power generation rate of 18 9 kw/ft and withstand levels of 213 kw/ft without fuel failure during operating tranciente at the nnxirnum expected fuel exposure." |
| : 2. (ACR2 letter dated March 14, 1967 - Report on Browns Ferry Duclear lower Station) | | : 2. (ACR2 {{letter dated|date=March 14, 1967|text=letter dated March 14, 1967}} - Report on Browns Ferry Duclear lower Station) |
| "A linear heat generation rate of 28 kW/ft is used by the applicant as a fuel element dtunage limit. Experimental verification of this criterion is incomplete, and the applicant plans to conduct additional tests. The committee recomende that cuch tects include heat generation rates in excess of those calculated for the worst anticipated transient and fuel burnups comparable to the naximum expected in the reactor." | | "A linear heat generation rate of 28 kW/ft is used by the applicant as a fuel element dtunage limit. Experimental verification of this criterion is incomplete, and the applicant plans to conduct additional tests. The committee recomende that cuch tects include heat generation rates in excess of those calculated for the worst anticipated transient and fuel burnups comparable to the naximum expected in the reactor." |
| To provide further information on these questions, the le:.d rods in Caxton CoreIII will operate-at an expected peak linear power density of 21.2 kw/ft and to 45,000 !GD/MTi> which is expected to provide a satisfactory response to the' ACE 5 cugge E ons. Purther, the operating conditions of thece rode vill with high probability exceed the desi 1 peak linear power density of the Diablo Canyon and Zion plants of 18 9 hw ft. | | To provide further information on these questions, the le:.d rods in Caxton CoreIII will operate-at an expected peak linear power density of 21.2 kw/ft and to 45,000 !GD/MTi> which is expected to provide a satisfactory response to the' ACE 5 cugge E ons. Purther, the operating conditions of thece rode vill with high probability exceed the desi 1 peak linear power density of the Diablo Canyon and Zion plants of 18 9 hw ft. |
|
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217D4031999-10-0606 October 1999 Summarizes Series of Four Revs That Have Been Made to SNEC Emergency Response Procedure & Emergency Plan Since 970408. Revs Include Changes to Reflect Current Site Conditions & Changes in Organizational Structure ML20216J9811999-10-0404 October 1999 Forwards Insp Rept 50-146/99-202 on 990830-0902.No Violations Noted.Insp Consisted of Selective Exams of Procedures & Representative Records,Interviews with Personnel & Observations of Activities in Progress ML20209B9971999-06-29029 June 1999 Forwards 1998 Annual Rept for Saxton Nuclear Experimental Corp (Snec).Rept Covers Period Beginning 980101-981231 ML20195E0131999-06-0303 June 1999 Provides Encl Info as Evidence of Jcp&L,Meed & Penelec Commitment to Assure Continued Financial Support of Decommissioning Efforts of SNEC ML20206G6341999-05-0303 May 1999 Requests Info on How SNEC Will Show Compliance with Requirements in 10CFR50.75 on How SNEC Will Provide Reasonable Assurance That Funds Will Be Available for Completion of Decommissioning Process for Plant ML20206F6451999-04-29029 April 1999 Forwards 1998 Annual Radioactive Release Rept for SNEC & Rev 0 to Odcm. Explanations of Attachments 1-9,listed ML20206D1211999-04-27027 April 1999 Informs of Completion of Acceptance Review of Saxton Nuclear Experimental Facility License Termination Plan Submitted on 990203.Concludes That LTP Does Not Contain Sufficient Info at Present Time to Initiate Detailed Review ML20206G0351999-04-27027 April 1999 Forwards Proprietary 10CFR20.2206(b) Personnel Exposure Rept for Saxton Nuclear Experimental Corp.Rept Contains Info Required to Identify Total Number of Individuals for Whom Personnel Monitoring Was Required.Proprietary Info Withheld ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20204H7851999-03-22022 March 1999 Forwards Insp Rept 50-146/99-201 on 990216-18.No Violations Noted.Nrc Questionnaire Re Yr 2000 Concerns Encl ML20198A4031998-12-10010 December 1998 Forwards Insp Rept 50-146/98-204 on 981013-1106.No Violations Noted.No Response to Ltr Required ML20154K1181998-10-13013 October 1998 Forwards Insp Rept 50-146/98-203 on 980914-17.No Violations Noted ML20153C4241998-09-21021 September 1998 Responds to Requesting NRC Review Aspects of 980624 Application from Saxton Nuclear Experimental Corp & Gpu Nuclear,Inc for Regulatory Relief from DOT Shipping Requirements.Srvts Should Be Classified as LSA-III ML20237D9951998-08-24024 August 1998 Informs That Staff Does Not Object to Blending of Guide Blocks to Lower Core Plate & Determined That Guide Blocks & Plate Permanently Connected ML20236N8891998-06-24024 June 1998 Submits Two Complete Copies of Gpu Nuclear'S Requests for Exemptions,Re Shipment of Sg,Pressurizer & Reactor Vessel. Detailed Exemption Requests & Supporting Documentation Are Provided in Enclosed Attachments ML20249A2391998-06-11011 June 1998 Corrects 980420 Safety Evaluation for Amend 15 to License DPR-04 & 980409 EA & Finding of No Significant Impact.Ea Section 3.2.2 Does Rate Should Be Changed to 200 Msv Per H ML20249A6901998-06-11011 June 1998 Forwards Insp Rept 50-146/98-202 on 980511-13.No Violations Noted ML20248D6981998-05-28028 May 1998 Forwards Annual Rept & Radiological Environ Monitoring Rept for 970101-1231 for Saxton Nuclear Experimental Corp ML20216B6441998-05-0808 May 1998 Forwards Request for Addl Info Re Saxton Nuclear Experimental Facility.Various Facility Components Will Be Shipped off-site for Disposal as Radwaste ML20217A9641998-04-20020 April 1998 Forwards Amend 15 to License DPR-4 & Safety Evaluation. Amend Allows Decommissioning of Saxton Nuclear Experimental Corp Facility ML20217H2231998-04-17017 April 1998 Forwards Personnel Exposure Rept for Saxton Nuclear Experimental Corp for Calendar Year 1997.W/o Encl ML20216D0611998-04-0909 April 1998 Forwards Environ Assessment & Finding of No Significant Impact & Being Sent to Office of Federal Register for Publication.Concludes That No Significant Environ Impact Attributable to Proposed Action ML20217P7701998-03-31031 March 1998 Provides Results of Calculations Performed to Evaluate Dose to Public to Be Expected from Hypothetical Spill of Tritiated Water Being Stored in SNEC Facility Containment Vessel.Scenarios Found to Have No Significant Public Health ML20217P4181998-03-0303 March 1998 Provides Response to Question 7 of RAI Dtd 980128.Response Will Be Incorporated as Suppl 1 to Facility Decommissioning Environ Rept ML20203A5771998-02-0909 February 1998 Forwards RAI Re Amend Request for License DPR-4 Submitted 981125.Response Requested to Be Provided within 30 Days of Date of Ltr ML20202F6961998-02-0909 February 1998 Provides Response to Questions Re Apparent Undocumented Changes to Saxton Nuclear Experimental Corp Decommissioning QA Plan ML20202B2351998-02-0303 February 1998 Responds to 980128 RAI Re TS Change Request 59.Response Includes Proposed Revised Pages to Facility License,Ts, Updated Sar,Decommissioning QA Plan & Figures to Post Shutdown Activities Rept.W/Certificate of Svc ML20199F2321998-01-27027 January 1998 Forwards Request for Addl Info Re Amend to License DPR-4. Responses Requested to Be Provided within 30 Days of Dtd Ltr ML20217J7751997-10-0909 October 1997 Submits Reply to Discussing Decommissioning Activities at Facility.Decommissioning Requested to Be Delayed for 25 Yrs to Allow for Addl Radioactive Decay ML20211C2371997-09-16016 September 1997 Forwards Rev 0 to Procedure 6575-PLN-4542.09, SNEC Facility Process Control Program, for Review & Approval.Activities Will Be Initiated Starting W/Item 1.2.2.3 of Figure 2.2-4 of Decommissioning Plan When Approval of Tscr 59 Is Obtained ML20210Q2211997-08-21021 August 1997 Forwards Response to Requests for Addl Info & 0806.Info Suppls Previous Responses to Questions,Addresses Recent Questions on ODCM & Incorporates Editorial Comments Commited by Telcon.Revised TS & Updated SAR Encl ML20217H4291997-08-0606 August 1997 Forwards RAI Re Amend Request for License DPR-4.Reply Requested within 30 Days of Dtd Ltr ML20217G9271997-08-0505 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transfered from Regional Ofc to Nrr.All Activities Re Non-Power Reactors Including Licensing,Insp & Operator Licensing Will Be Responsibility of NRR ML20141C6541997-06-16016 June 1997 Clarifies Statements in Safety Insp Rept 50-146/97-01 for Saxton Nuclear Experimental Corp Facility,That Do Not Reflect Utils Practices or Intentions ML20141C4001997-06-16016 June 1997 Forwards Procedure 6575-ADM-4500.06, Emergency Response Procedure & Emergency Plan, That Was Inadvertently Overlooked & Not Included as Attachment in Submittal, ML20217Q5871997-06-11011 June 1997 Provides Concerns & Suggestions Re Gpu Decommissioning Plan ML20140C1271997-05-30030 May 1997 Forwards Response to 970408 RAI Re TS Change Request 59 & Revised Pages to Change Request Which Includes Rev to Original Text Based Upon Response Provided ML20140C9261997-05-30030 May 1997 Forwards Responses to 970424 RAI Re Questions Resulting from Review of SNEC Decommissioning QA Program ML20138B6261997-04-24024 April 1997 Forwards Request for Addl Info Re Amend Request for License DPR-4.Response Requested within 30 Days of Ltr Date ML20137R7911997-04-0909 April 1997 Forwards RAI Re Request for Amend to Facility License DPR-4 ML20140D3761997-04-0303 April 1997 Forwards 10CFR20.2206(b) 1996 Personnel Exposure Rept for Snec,Containing Info Required to Identify Total Number of Individuals for Whom Personnel Monitoring Was Required & Statistical Summary of Personnel Monitoring Info.W/O Encl ML20140B7131997-03-18018 March 1997 Forwards Insp Rept 50-146/97-01 on 970127-29.No Violations Noted ML20136E2041997-03-0606 March 1997 Forwards Notice of Consideration of Issuance of Amend to Facility License & Proposed NSHC Determination & Opportunity for Hearing Re 961125 Request to Amend Facility License DPR-4 ML20134K1961997-02-11011 February 1997 Expresses Appreciation for Participation in 970128 Public Meeting on Post-Shutdown Decommissioning Activities Rept for Facility.Transcript of Meeting Encl ML20149M6621997-01-22022 January 1997 Forwards Copy of Notice That Appeared in 961219 Federal Register Re Public Meeting on post-shutdown Decommissioning Activities Rept for SNEC Facility & Agenda for Meeting ML20133N4001997-01-21021 January 1997 Informs That NRC Planning to Hold Public Meeting on post- Shutdown Decommissioning Activities Rept for SNEC Facility in Sexton,Pa on 970128 ML20133P9381997-01-21021 January 1997 Forwards Insp Rept 50-146/96-01 on 961119-21.No Violations Noted ML20133E1121997-01-0808 January 1997 Informs That NRC Planning to Hold Public Meeting on post- Shutdown Decommissioning Activities Rept for SNEC Facility on 970128 ML20134P3351996-11-25025 November 1996 Forwards TS Change Request 59,submitting Decommissioning TSs ML20134L7311996-11-0808 November 1996 Submits site-specific Cost Estimate for Saxton Nuclear Experimental Corp Facility as Required by 10CFR50.82(a)(8)(ii) & Satisfies Commitment to Have an Approved Quality Assurance Plan,Per 10CFR71.101 1999-06-03
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D4031999-10-0606 October 1999 Summarizes Series of Four Revs That Have Been Made to SNEC Emergency Response Procedure & Emergency Plan Since 970408. Revs Include Changes to Reflect Current Site Conditions & Changes in Organizational Structure ML20209B9971999-06-29029 June 1999 Forwards 1998 Annual Rept for Saxton Nuclear Experimental Corp (Snec).Rept Covers Period Beginning 980101-981231 ML20195E0131999-06-0303 June 1999 Provides Encl Info as Evidence of Jcp&L,Meed & Penelec Commitment to Assure Continued Financial Support of Decommissioning Efforts of SNEC ML20206F6451999-04-29029 April 1999 Forwards 1998 Annual Radioactive Release Rept for SNEC & Rev 0 to Odcm. Explanations of Attachments 1-9,listed ML20206G0351999-04-27027 April 1999 Forwards Proprietary 10CFR20.2206(b) Personnel Exposure Rept for Saxton Nuclear Experimental Corp.Rept Contains Info Required to Identify Total Number of Individuals for Whom Personnel Monitoring Was Required.Proprietary Info Withheld ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20248D6981998-05-28028 May 1998 Forwards Annual Rept & Radiological Environ Monitoring Rept for 970101-1231 for Saxton Nuclear Experimental Corp ML20217H2231998-04-17017 April 1998 Forwards Personnel Exposure Rept for Saxton Nuclear Experimental Corp for Calendar Year 1997.W/o Encl ML20217P7701998-03-31031 March 1998 Provides Results of Calculations Performed to Evaluate Dose to Public to Be Expected from Hypothetical Spill of Tritiated Water Being Stored in SNEC Facility Containment Vessel.Scenarios Found to Have No Significant Public Health ML20217P4181998-03-0303 March 1998 Provides Response to Question 7 of RAI Dtd 980128.Response Will Be Incorporated as Suppl 1 to Facility Decommissioning Environ Rept ML20202F6961998-02-0909 February 1998 Provides Response to Questions Re Apparent Undocumented Changes to Saxton Nuclear Experimental Corp Decommissioning QA Plan ML20202B2351998-02-0303 February 1998 Responds to 980128 RAI Re TS Change Request 59.Response Includes Proposed Revised Pages to Facility License,Ts, Updated Sar,Decommissioning QA Plan & Figures to Post Shutdown Activities Rept.W/Certificate of Svc ML20211C2371997-09-16016 September 1997 Forwards Rev 0 to Procedure 6575-PLN-4542.09, SNEC Facility Process Control Program, for Review & Approval.Activities Will Be Initiated Starting W/Item 1.2.2.3 of Figure 2.2-4 of Decommissioning Plan When Approval of Tscr 59 Is Obtained ML20210Q2211997-08-21021 August 1997 Forwards Response to Requests for Addl Info & 0806.Info Suppls Previous Responses to Questions,Addresses Recent Questions on ODCM & Incorporates Editorial Comments Commited by Telcon.Revised TS & Updated SAR Encl ML20141C6541997-06-16016 June 1997 Clarifies Statements in Safety Insp Rept 50-146/97-01 for Saxton Nuclear Experimental Corp Facility,That Do Not Reflect Utils Practices or Intentions ML20141C4001997-06-16016 June 1997 Forwards Procedure 6575-ADM-4500.06, Emergency Response Procedure & Emergency Plan, That Was Inadvertently Overlooked & Not Included as Attachment in Submittal, ML20217Q5871997-06-11011 June 1997 Provides Concerns & Suggestions Re Gpu Decommissioning Plan ML20140C1271997-05-30030 May 1997 Forwards Response to 970408 RAI Re TS Change Request 59 & Revised Pages to Change Request Which Includes Rev to Original Text Based Upon Response Provided ML20140C9261997-05-30030 May 1997 Forwards Responses to 970424 RAI Re Questions Resulting from Review of SNEC Decommissioning QA Program ML20140D3761997-04-0303 April 1997 Forwards 10CFR20.2206(b) 1996 Personnel Exposure Rept for Snec,Containing Info Required to Identify Total Number of Individuals for Whom Personnel Monitoring Was Required & Statistical Summary of Personnel Monitoring Info.W/O Encl ML20134P3351996-11-25025 November 1996 Forwards TS Change Request 59,submitting Decommissioning TSs ML20134L7311996-11-0808 November 1996 Submits site-specific Cost Estimate for Saxton Nuclear Experimental Corp Facility as Required by 10CFR50.82(a)(8)(ii) & Satisfies Commitment to Have an Approved Quality Assurance Plan,Per 10CFR71.101 ML20134F3221996-10-25025 October 1996 Forwards SNEC Facility USAR to Incorporate Changes Commensurate W/Snec Facility Condition as It Makes Transition from Safstor to Active Decommissioning & Dismantlement ML20129G9531996-09-30030 September 1996 Provides Clarification of Approach Util Proposes to Fulfill Requirements Specified in New 50.82 Re SNEC Facility ML20117C2011996-08-20020 August 1996 Forwards Addendum to 1995 Saxton Nuclear Experimental Corp 960524 Annual Rept ML20115K0511996-07-18018 July 1996 Forwards Responses to 960606 Request for Addl Info Re Questions Resulting from Review of SNEC Facility Decommissioning Plan & Environ Rept ML20117N6901996-06-17017 June 1996 Informs NRC That Transfer to Gpun management-related Responsibilities for SNEC Facility as Set Forth by Order Approving Transfer Issued on 960510 Completed.Signed Copy of Amend 23 to Indemnity Agreement B-5 Encl ML20112D0091996-05-24024 May 1996 Responds to Request for Addl Info Re Tech Spec Change Request 57,which Addresses Proposed Expansion of Permissible Work Scope at SNEC Facility ML20107K0711996-04-24024 April 1996 Submits Response to RAI Re TS Change Request 57 Which Addresses Proposed Expansion of Permissible Work Scope at Facility ML20101C5621996-03-13013 March 1996 Provides Addl Info in Support of 951121 LAR ML20101B8741996-03-0808 March 1996 Requests NRC Approval to Leave Shield Blocks & Steel Plates in SNEC Facility Containment Vessel,In Place After Completion of Reactor/Fuel Storage Cavity Characterization Activities ML20100P3731996-02-28028 February 1996 Submits Revs to No Significant Hazards Consideration Analysis Based on Conversation W/Snec Facility Project Manager Re Deficiencies Found in Text Supporting Proposed Changes Contained in SNEC Tscr 57 ML20100H6121996-02-16016 February 1996 Responds to 950818 RAI Re Inadvertent Breach of Facility Containment Vessel Liner During Core Bore Operations in Support of Characterization.Rev 0 to Program 6250-PGD-2720 & Rev 0 to Procedure 6575-ADM-4500.07 Encl ML20149K8021996-02-16016 February 1996 Forwards Rev 0 of SNEC Facility Decommissioning Plan ML20100F4571996-02-0202 February 1996 Forwards Application for Amend to License DPR-4,proposing Expansion of Permitted Principal Activities within Exclusion Area,Certificate of Service & Safety Evaluation & Determination of No Significant Hazards Considerations ML20097G3341995-12-21021 December 1995 Requests Consideration of Amend Application Re Transfer of All mgt-related Responsibilities to SNEC ML20087H8211995-08-11011 August 1995 Forwards Agreement Which Describes & Governs Relationship Between SNEC & Gpun,In Response to NRC RAI Re TS Change Request 56 ML20087F0941995-08-0808 August 1995 Informs of Recent Action by Licensee Board of Directors to Name Fd Hafer as SNEC President as Replacement for Je Hildebrand & Ga Kuehn to Position of SNEC Vice President & General Manager Replacing Ba Good ML20087J7541995-07-27027 July 1995 Forwards Responses to RAI Re 15 Day Rept on Inadvertent Breach of Snef Containment Vessel Liner & Status Activities Associated W/Installation of Permanent Plug or Seal.Root Cause/Human Performance Evaluation Results Encl ML20086B8421995-06-28028 June 1995 Forwards Saxton Nuclear Experimental Corp 1994 Annual Rept for Saxton Nuclear Experimental Facility for 940101-941231 ML20086A5481995-06-23023 June 1995 Forwards Addendum to TS Change Request 56 to License DPR-4, Revising TS Pages 1,2 & 8 to Change Organization Performing Remainder of Characterization Activities & Future Decommissioning Activities to Assure Linkage W/Licensee ML20092B3441995-06-0707 June 1995 FOIA Request for Correspondence Between Westinghouse & AEC Re Westinghouse Work on Saxton Experimental Reactor in Saxton,Pa Between Years of 1956 & 1974 ML20084J2641995-06-0202 June 1995 Forwards Request for Amend to DPR-4 TSs (TS Change Request 56) ML20082K2891995-04-0606 April 1995 Provides Addl Info Re 950327 Meeting Between Gpu & NRC Concerning Idea of Independent Inspector.News Article from Altoona Mirror Which Author Believe Accurately Represents Bedford County Commissioners Viewpoint Encl ML20076M3371994-10-28028 October 1994 Responds to RAI Re TS Change Request 55 ML20072C2181994-08-0808 August 1994 Forwards Application for Tscr to Revise Content & Format of Existing TS & Analysis Applying Standards of 10CFR50.92 in Making Significant Hazards Considerations Determination ML20062L7301993-12-20020 December 1993 Forwards Responses to NRC Questions Resulting from Review of TS Change Request 54.Revised TS Pages Also Encl ML20057A6371993-09-0808 September 1993 Forwards 10CFR20.407 Personnel Exposure Rept for 1992.Late Submittal Is Result of Administrative Error,Identified by Internal QA Audit.Corrective Action Taken ML20056G8191993-08-31031 August 1993 Forwards Penelec/Gpu Internal Affairs Dept Williamsburg Incident Investigation 89-WM-2, in Response to 930810 Telcon ML20045G6991993-06-23023 June 1993 Forwards TS Change Request 54 to License DPR-4,including Facility Characterization as Activity Permissible in TS 1999-06-03
[Table view] |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _
i i '* t*? ,
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'; [ m SAXT6N NUCLEAR EXPERIMENTAL CU POliATIOW th GENERAL P U D L. l C UTILITICS SYSTEM
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ff JC o,,..w,,,so,,,,c,.... gy, n W s' > s f225' P. O. Bom 542, Reading. Po. 19603 Telephone: Area 215 929 3601 P. O. Bon 99, Santon, Pa. 16678 Ateo Old . 63$ 2737
/sucust 7 1968 l!V .h Docket !!o. 50-lL6 Licence Ilo. DTR h t v: . 1 Mr. Peter A. Morris, Director Division of Reactcr Licencing United 2tates Atomic Energ;' C;: mission Wachincton, D. C. 2WS O
Dec.r Mr, Marric:
During the next few months the Eaxton Iluclear Experitea Al
- Corporation (E!EC) will apply for an atenument to the Technical Epecifications to operate a Core III in the Saxton Henctor, and for an extension of its operat ng license (DTR L) which expires in December 1968. The purpose of this letter is to outline briefly the experimental programs planned, and to state the joint E!EC-Weetinghouse position on the continued operation of Saxton. We believe that these programs are cignificant not only to ElEC and Westinghouce, but also to the entire nuclear industry and the AEC, in the field of WR and water reactor technology generally.
The Core III progra.m is sumarized below and in subcequent paragraphs, those items of particular public interest will be discucced more fully. With the exception of Iter B-3 these programs are funded by Westinghouse and GPU.
A. Training of reactor operators and supervisory personnel.
B. Development and proof testing of fuel a::semblies for NR reactors, ac follows:
- 1. The' irradiation of the plutonium enriched UO,.3 Zircalcy clad rods from Core II to a combination of linear power density and depletion which will certify the power-bornup capability of oxide fuel elements being used for WR's and which will demonstrate power-burnup design limits for ;
this type of fuel element.
i e 2. The irradiation of reference WR fuel elements under .
loading cycling conditions simulating those expected in IVR's operating as load follow planta on utility power cystems.
l ALC- + 3 The continued exposnre of the pu02 -UO2 fuel from Core II under the AEC-Euratom program. ff o w;g % m n we DEMok91-37 PDR
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Mr. I'.arris Auguct 7, 1968
- 1. . 'Ihe ccnluct of taxiliary testc to identify fatigue lititc, and in-pile creep behavior of Z'ircaloy cladding and the effects of fuel ten:perature cycling on ficcion gaa releare.
Referrin.7 to item A, Zaxtra hac played a cignificant role in the pact by providinr training and power reactor oper1 ting experience for reactor operatort and cupervicory perconnel. Thic role, of a traininc facility for utility 1 rcer.nel who will be engaged in the cperation of IWR's v3.ll be exranied in the future. Both CI;EC and Westinghouse have a heavy cched.11c of training comitttente extending into 1972. There comittments include training for other than Westinghouac euctoterc; i.e., Du.ke Power Company, Onin Inblic lower Dictrict and Baltimore Gac and Electric Ccapany. Irecen; planc are to train about 100 cupervicory personnel per year.
O The objective of Item b-1 in a dernonstration of fuel performnce j in responce ta questionc which have been raicel by the Commiscion's Advisory Cer:.ittee on heactor Cafeguard: (ACRJ), and which are generally applicable to IWR' c being decigned and built toAay; 1.e. , the following "astericked" quectiont):
- 1. (Docket I;o. 50-275 - Diablo Canyon PcAR, 3rd Eupplement, Quention V. B. I.) (Docket No. 50-295 - Zion PSAR, Vol. 3, Queation V. B. I.)
" Provide a detail '. O ccucsion of the experimental programs which are in progress or will be accomplished prior to operation to demonstrate the proposed core can be safely operated at a linear power generation rate of 18 9 kw/ft and withstand levels of 213 kw/ft without fuel failure during operating tranciente at the nnxirnum expected fuel exposure."
- 2. (ACR2 letter dated March 14, 1967 - Report on Browns Ferry Duclear lower Station)
"A linear heat generation rate of 28 kW/ft is used by the applicant as a fuel element dtunage limit. Experimental verification of this criterion is incomplete, and the applicant plans to conduct additional tests. The committee recomende that cuch tects include heat generation rates in excess of those calculated for the worst anticipated transient and fuel burnups comparable to the naximum expected in the reactor."
To provide further information on these questions, the le:.d rods in Caxton CoreIII will operate-at an expected peak linear power density of 21.2 kw/ft and to 45,000 !GD/MTi> which is expected to provide a satisfactory response to the' ACE 5 cugge E ons. Purther, the operating conditions of thece rode vill with high probability exceed the desi 1 peak linear power density of the Diablo Canyon and Zion plants of 18 9 hw ft.
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, ; ore III will be cetposed of 21 acccmblies. The 12 peripheral ascemblies will be UO2 etainlecc steel clad accemblier frorn Core I and Core II.
The nine center a.;semblies will concict of two new assemblics for the load fnllow erperiment and seven assatblies consisting of new cheletons loaded cith Zr clal luo2-UO2 rodc frem Core II. ,
These are referred to as the Loose-Lattice Accemblies and consist of fuel rolc and water fille 1 tubec placed in alternate positions in the lattice.
The a1 vantage of the Looce-Lattice configuration is that it permits a large number of rode in the core to run at hi;,n linear power dencity without exceeding overall limitations in thermal output from the core.
I Inc de.:ign of Core III is now comp 3ete and arrangement: have beer.
made for the reconstruction of the Looce-Lattice Assemblies at the .s'estinghouce j Toct-Irradiation heility at Waltz Mill during the second half of 1963. The '
two load follow accemblier will be built concurrently.
In parallel with this, action is being taken in the following areac
- 1. An application is being prepared to permit operation of the reactor with Core III. This will be cubmitted by August 31, 1963, and we will need approval by December 31,1%B.
- 2. Action is being taken to extend the ENEC corporate charter for a period of five yearc; i.e. , to May 197h, and to extend the EHEC agreemente with Westinghouse and the GPU operating subsidiariec for the financial support of Saxton's operations. An application for an extencion of the Saxton operating license (DPR 4) will be cubmitted when these steps have been completed.
3 The plant modificatient and inspection program as described in the document entitled "Saxton Loss-of-Coolant Accident Prevention \
and Protection" will be completed before the startup of Core III ccheduled for February 1969 The schedule we have set for these tasks reflects our concern to accceplich the programs and obtain cignificant recults as quickly as possible.
We are cure that ,vou will chare this concern, and we will cooperate with the staf f at every ctage of the regulatory processes. Please let us know if there are any specific areas in which we can assist these procccces.
Very truly yours,
/l]
R. E. Neidig 2.,c <t President CC: Pr. G. F. Trowbridge
- . _ _ _ _ _ _ _ _ _ _ - _ -